Sorption procedure for recovery of 90Sr from nuclear fuel reprocessing solutions and its purification. I. Recovery of 90Sr

A possibility was studied of sorption recovery of 90Sr from raffinates resulted from the reprocessing of nuclear fuel. A method was suggested for selective recovery of strontium with vinylpyridine ampholyte VPK in the presence of masking additives of complexing agents [citric and chromotropic acids (CTA and CHA, respectively)]. Optimal conditions of the process are as follows: in the presence of CTA-CTA: ΣMe = 0.5 : 1 at pH 8, and in the presence of CHA-CHA: ΣMe = 1:1 at pH 7-9; the resin in the Na form. Under these conditions the main part of inpurities is transferred into the filtrate. The process was tested with a highly radioactive solution. Thea authors have obtained the following factors of purification of 90Sr: with respect to γ-emitting radionuclides 47, β-emitting radionuclides 5, Fe 7, Ni 5, Cr 17, Al 48, Mn 5, and rare-earth metals 3. Approximately 98% of strontium was recovered